Irradiation surveillance program as applied in Switzerland
Conference
·
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6187057
Present irradiation surveillance programs are based mainly on Charpy V-notch impact bend specimens. The nil-ducility transition temperature shift as a relative measure of embrittlement is determined from the transition temperature curves. Under the assumption of identical shifts of Charpy V-notch transition curves and the pressure vessel material fracture behavior, the pressure-temperature limits for the reactor pressure vessel are derived. Problems inherent in the use of Charpy V-notch impact bend specimens are discussed and an approach to overcome them presented. The surveillance programs for a pressurized water reactor and boiling water reactor are described.
- Research Organization:
- Swiss Nucl Saf Div, Wuerenlingen, Switz
- OSTI ID:
- 6187057
- Report Number(s):
- CONF-800609-
- Conference Information:
- Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
- Country of Publication:
- United States
- Language:
- English
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